Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F16%3A00460360" target="_blank" >RIV/61389021:_____/16:00460360 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1088/0029-5515/56/6/066008" target="_blank" >http://dx.doi.org/10.1088/0029-5515/56/6/066008</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/0029-5515/56/6/066008" target="_blank" >10.1088/0029-5515/56/6/066008</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER

Popis výsledku v původním jazyce

Results from three-dimensional modeling of plasma edge transport and plasma–wallninteractions during application of resonant magnetic perturbation (RMP) fields for control ofnedge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The fulln3D plasma fluid and kinetic neutral transport code EMC3-EIRENE is used for the modeling.nFour characteristic perturbed magnetic topologies are considered and discussed with referencento the axisymmetric case without RMP fields. Two perturbation field amplitudes at full andnhalf of the ITER ELM control coil current capability using the vacuum approximation arencompared to a case including a strongly screening plasma response. In addition, a vacuumnfield case at high q95 = 4.2 featuring increased magnetic shear has been modeled.nFormation of a three-dimensional plasma boundary is seen for all four perturbed magneticntopologies. The resonant field amplitudes and the effective radial magnetic field at the separatrixndefine the shape and extension of the 3D plasma boundary. Opening of the magnetic field linesnfrom inside the separatrix establishes scrape-off layer-like channels of direct parallel particlenand heat flux towards the divertor yielding a reduction of the main plasma thermal and particlenconfinement.This impact on confinement is most accentuated at full RMP current and is stronglynreduced when screened RMP fields are considered, as well as for the reduced coil current cases.

Název v anglickém jazyce

Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER

Popis výsledku anglicky

Results from three-dimensional modeling of plasma edge transport and plasma–wallninteractions during application of resonant magnetic perturbation (RMP) fields for control ofnedge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The fulln3D plasma fluid and kinetic neutral transport code EMC3-EIRENE is used for the modeling.nFour characteristic perturbed magnetic topologies are considered and discussed with referencento the axisymmetric case without RMP fields. Two perturbation field amplitudes at full andnhalf of the ITER ELM control coil current capability using the vacuum approximation arencompared to a case including a strongly screening plasma response. In addition, a vacuumnfield case at high q95 = 4.2 featuring increased magnetic shear has been modeled.nFormation of a three-dimensional plasma boundary is seen for all four perturbed magneticntopologies. The resonant field amplitudes and the effective radial magnetic field at the separatrixndefine the shape and extension of the 3D plasma boundary. Opening of the magnetic field linesnfrom inside the separatrix establishes scrape-off layer-like channels of direct parallel particlenand heat flux towards the divertor yielding a reduction of the main plasma thermal and particlenconfinement.This impact on confinement is most accentuated at full RMP current and is stronglynreduced when screened RMP fields are considered, as well as for the reduced coil current cases.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

BL - Fyzika plasmatu a výboje v plynech

OECD FORD obor

—

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2016

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Nuclear Fusion

ISSN

0029-5515

e-ISSN

—

Svazek periodika

56

Číslo periodika v rámci svazku

6

Stát vydavatele periodika

AT - Rakouská republika

Počet stran výsledku

22

Strana od-do

—

Kód UT WoS článku

000376446000012

EID výsledku v databázi Scopus

2-s2.0-84975518970